Separation method of neptunium from reprocessed uranium by TEVA-UTEVA extraction chromatography column

被引：0
作者：
机构：
[1] China Institute of Atomic Energy, Beijing 102413
[2] Nuclear and Radiation Safety Center, Ministry of Environmental Protection
来源：
Su, Y.-L. | 1600年 / Atomic Energy Press卷 / 48期
关键词：
Neptunium; Separation; TEVA-UTEVA extraction chromatographic method; Uranium product;
D O I：
10.7538/yzk.2014.48.05.0786
中图分类号：
学科分类号：
摘要：
An efficient and quantitative extraction chromatographic method using commercially available TEVA resin and UTEVA resin was developed for the separation of neptunium from reprocessed uranium. Before the sample was loaded onto TEVA column, neptunium was adjusted to Np(IV), and then the eluent of 2 mol/L HNO3-0.2 mol/L H2C2O4 was loaded to elute the neptunium, the uranium in eluent after diluting was retained on UTEVA resin, while Np(IV) was stripped from the resin. The average recovery of neptunium of the whole separation procedure is about 94% and the decontamination coefficient of uranium is more than 104.
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页码：786 / 791
页数：5
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共 10 条
  • [1] Uchiyama G., Hotoku S., Fuj I.S., Et al., Np separation process in reprocessing using butyraldehde as a Np(VI) reductant, 1990 Annual Meeting of the Atomic Energy Society of Japan, pp. 21-30, (1990)
  • [2] Uchiyama G., Hotoku S., Kihara T., Et al., Process study on neptunium separation using salt-free reduction reagent, Solvent Extraction'90, pp. 675-681, (1992)
  • [3] Kolarik Z., Schuler R., Separation of neptunium and plutonium in the Purex process, Extraction'84, pp. 105-120, (1984)
  • [4] Groh H.J., Schcea C.S., Progress in Nuclear Energy Series, III: Process Chemistry, 4, pp. 507-547, (1970)
  • [5] Moreno J.M.B., Betti M., Alonso J.I.G., Determination of neptunium and plutonium in the presence of high concentrations of uranium by ion chromatography-inductively coupled plasma mass spectrometry, Journal Analytical Atomic Spectrometry, 12, pp. 355-361, (1997)
  • [6] Maillard C., Agniel S., Boyer-Deslys V., Separation for analytical purpose of Np traces from different solutions of fuel reprocessing, Atalante, 7, pp. 697-702, (2012)
  • [7] Wang X., Lin C., Liu J., Et al., Analysis of micro <sup>237</sup>Np in uranium, Journal of Nuclear and Radiochemistry, 24, 1, pp. 16-25, (2002)
  • [8] Ji Y., Li J., Determination of trace neptunium and plutonium by ICP-MS, Journal of Nuclear and Radiochemistry, 30, 2, pp. 103-107, (2008)
  • [9] Crozet M., Guigue M., Separation of actinides by extraction chromatography prior to X-ray fluorescence measurement for analytical control of a Purex test, Radiochim, 95, pp. 629-635, (2007)
  • [10] Horwitz E.P., Dietz M.L., Chiarizia R., Separation and preconcentration of actinides by extraction chromatography using a supported liquid anion exchanger application to the characterization of high-level nuclear waste solutions, Analytica Chimica Acta, 310, pp. 63-78, (1995)
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